ML19275A828
| ML19275A828 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/27/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19275A825 | List: |
| References | |
| NUDOCS 7910190157 | |
| Download: ML19275A828 (6) | |
Text
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UNITED STATES y'
'g NUCLEAR REGULATORY COMMisslON
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j WASHINGTON, D. C. 20555 8
MAINE YANKEE ATOMIC POWER COMPANY
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DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 45 License No. DPR-36 1.
The Nuclear ~ Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated September 16, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's reguhtions; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
1180 248 C
\\S 7910190 i
. Accordingly, the license is amended by changes to the Technical
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2.
Specifications as indicated in the attachment to this license amendment, and paragraph 2.B.(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
(b)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 45, are The licensee hereby incorporated in the license.
shall operate the facility in accordan e with the Technical Specifications.
This license amendment is effective as of the date of its 3.
issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Eh V
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 27, 1979 9
1180 249.
ATTACHMENT TO LICENSE AMENDMENT NO. 45 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET NO. 50-309 Revise Appendix A as follows:
Remove Pages Insert New Pages 4.6 4.6-3 4.6 4.6-3 9
1180 250
4.6 PERIODIC TESTING C
SAFETY INJECTION AND CONTAIN' TENT SPRAY-SYSTEMS U[
STEAM GENERATOR AUXILIARY FEED PUMPS MAIN STEAi! EXCESS FLOW CHECK VALVES Applies to the safety ir.jection system, the contain:ent spray Applicability:
system, chemical inj ectior. system, the containment cooling syster, the auxiliary feedwater system, and the main steam excess flow check valves.
To verify that the subj ect systems will respond promptly and Objective:
perform their intended functions, if required.
Specification-SAFETY INJECTN AND COSTAINMENT SPRAY SYSTE!!S A.
The following tests will be performed conthly whenever plant conditions 1.
are as defined in Secticn 3.6.A of these Specifications.
Emergency Co're Cooling System (ECCS) pu=ps:
a.
Both operable high pressure safety injection (HPSI) pu=ps shall be tested by operating in the charging code.
Both operable low pressure safety injection (LPSI) pumps and both spray (CS) pu ps shall be tested by operating operable containment in the recirculation mode.
Acceptable performance shall be that pumps attain rated heads, 15 minutes, and that the associated instru-operate for at least centation and controls function properly, b.
ECCS Valves:
All autcratically operated valves that are required to operate toThe assure core flooding, or contain=ent spray shall be exercised.
volume control tank (VCT) outlet to charging pu=p suction valves shall be exercised through part travel and all other valves shall be visually checked to verify proper operating position.
The folicwing tests will be performed at each refueling interval:
2.
a.
ECCS Pu: ps:
One HPSI pu=p shall be flow tested at 100n psig discharge head.
100 psi One LPSI pu=p and one CS punp shall be flow tested at discharge head.
and LPSI flow During these tests flow distribution thru the HPS orifices will be checked.
Acceptable performance shall be that the pumps and orifices attain flow values used in the safety analysis.
Alternate pumps will be tested at each refueling interval, so that all pumps will be tested within any five year period.
Amendment No. 45 4.6-1 1180 251
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b.
ECCS Valves:
All automatically operated valves and the motor operated fill header root valves shall be exercised through their full travel in conjunction with the actuation signal testing set forth in Table 4.1-2 of Technical Specifications.
c.
Safety Injection Tanks:
Each safety injection tank will be flow tested by opening the. tank isolation valve sufficient to verify check valve operation.
d.
The correct position of each electrical and mechanical position stop for the following throttle valves shall be verified:
- 1) Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of maintenance on the valve when the HPSI system is required to be operable.
- 2) At least once per 4 months Valve Numbert HSI-M-11 HSI-M-12 HSI-M-21 HSI-M-22 HSI-M-31 HSI-M-32 e.
A flow balance test, as described in 4.6.A.2 above, shall be performed during shutdown to confirm the injection flow rates assumed in the Safety Analysis following completion of HPSI or LPSI system t.odifications that alter system flow characteristics.
3.
Contain=ent Spray Headers:
The containment spray flow no::les will be tested every five years. The test will consist of pressurizing the headers with air and verifying that the no::les are free of obstruction.
4.
Containment Isolation Valves:
.roked to the h'here practicable, each containment isolation valve shall
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position required to fulfill its safety function every three months. Those valves that cannot be tested without possible adverse effects during plant operation shall te tested during each cold shutdown if not tested during the previous three months.
B.
STEAM GENERATCR AUXILIARY FEED PUMPS During normal plant operation, each auxiliary feed pump shall be tested at quarterly intervals to demonstrate operability of pumps, system valves and instru=entation.
C.
MAIN STEAM EXCESS FLOW CHECK VALVES The mai. steam excess flow check valves shall be tested once every 6 weeks for
. of the valve disc through a distance of approximately one and one-half movement Amendment No. F57 45 i i 80 252 4.6-2
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inches. These valves wil; he tested through full travel distance during each refueling interval.
3*815 The safety injection syste= and the containment spray system are principal plant safeguards syste=s that are nomally operable during reactor operation.
Co=plete syste= tests cannot be performed when the reactor is operating because of their inter-relation with operating systems.
The =ethed of assurag oper-ability of these systems is a combination of co=plete system tests perfor=ed during refueling shutdowns and =onthly tests of active system components (pu=p:
and valves) which can be perfor=ed during reactor operation.
n e test interval is based on the judg=ent that = ore frequent testing would not significantly increase the reliability (i.e., the probability that the cc=cenent would operate when required), yet = ore frequent tests would result in increased wear over a long period of time.
The =onthly part travel exercising of the VCT outlet to charging pu=p suction valves, in lieu of the full travel exercise, is conducted to preclude an inter-ruption of nor=al plant operations. Redundant valves have been used te assure proper lineup in the event of ECCS actuation.
Other ECCS valves whose cpert: ion is not required to assure core flooding or centain=ent spray shall be tested during each refueling shutdown pericd in accordance with 2.b.
Verification tha_t the spray piping and no::les are cpen will be made initially by a suitably sensi:ive =ethod, and at least every five years thereafter.
Since all piping =aterial is all stainless steel, nor= ally in a dry condition, and with no plugging =echanism avr.ilable, the retes every five years is considered to be = ore than adequate.
Other syste=s that are i=portant to the emergency cooling function are the SI tanks, the ec=ponent cooling system and the service water system.
The SI tanks are a passive safety feature.
In accordance with the Specification 4.1 (Table 4.1-2, Item 11), the water volume ard pressure in the SI tanks are checked periodically. The cc.ponent cooling and service water syste=s operate when the reactor is in operation and are continuously =enitored for satisfactory perfor=ance.
The three month testing interval of the steam generator auxiliary feed pt.".ps verifies their operabi1N by recirculating water to the deminerali:ed water. tank.
Proper functioning of the steam turbine ad=ission valve and starting of the auxiliary feed pt=:p will de=enstrate the operability of the steam driven pump.
Verification of correct operation will be made both from instrumentation with the =ain control room and direct visual observation of the pu=ps.
The =ain steam, excess flow check valves serve to limit an excessive reactor coolant syste= cooldown rate and resultant reactivity insertion following a =ain steam break incident.
Their freedcm to move will be verified periedically.
1180 253 Amendment No. 45 4.6-3